URANIUM EXTRACTION AFFINAGE PROCESS Russian patent published in 2007 - IPC G21F9/06 G21C19/42 

FIELD: extraction processes for recovery of nuclear fuel, uranium concentrates, and uranium-containing reusable parts.

SUBSTANCE: proposed process for uranium extraction affinage includes dissolution of uranium concentrate at nitric acid excess of 0.75 - 1.0 mole/l and temperature of 80 - 95 °C; prior to extraction uranyl nitrate solution is doped with urea nitrate; post-extraction raffinate and alkali decanting product produced as result of re-extract treatment are separately subjected to carbamide denitration with solution being cooled down and urea nitrate sediment separated; decanting products produced in the process are mixed up and subjected to electrochemical treatment.

EFFECT: reduced nitric acid consumption and escape of raffinate-containing nitrate ions, escape of nitric oxides in uranium concentrate dissolution, and uranium loss with effluents.

7 cl, 5 dwg